Event Notification Report for November 26, 2013
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
11/25/2013 - 11/26/2013
Non-Agreement State
Event Number: 49583
Rep Org: AMERICAN ELECTRIC POWER
Licensee: AMERICAN ELECTRIC POWER
Region: 1
City: MOUNDSVILLE State: WV
County:
License #: GL 700076-18
Agreement: N
Docket:
NRC Notified By: DENISE POWELL
HQ OPS Officer: CHARLES TEAL
Licensee: AMERICAN ELECTRIC POWER
Region: 1
City: MOUNDSVILLE State: WV
County:
License #: GL 700076-18
Agreement: N
Docket:
NRC Notified By: DENISE POWELL
HQ OPS Officer: CHARLES TEAL
Notification Date: 11/26/2013
Notification Time: 14:27 [ET]
Event Date: 11/26/2013
Event Time: 12:00 [EST]
Last Update Date: 11/26/2013
Notification Time: 14:27 [ET]
Event Date: 11/26/2013
Event Time: 12:00 [EST]
Last Update Date: 11/26/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
DAN SCHROEDER (R1DO)
FSME EVENT RESOURCE (EMAI)
DAN SCHROEDER (R1DO)
FSME EVENT RESOURCE (EMAI)
PROCESS GAUGE SHUTTER CABLE FAILURE
The cable used to remotely operate the shutter for a fixed process gauge broke. The gauge is installed in a location that is not readily accessible by personnel. The normal position for the gauge is open. The gauge is currently open and in use. The licensee can manually close the shutter if needed. There were no personnel exposures.
The licensee has contacted the manufacturer to repair the cable.
The gauge is a Termo MeasureTech Model 5202, Serial Number B2813, containing 200 mCi of Cs-137.
The cable used to remotely operate the shutter for a fixed process gauge broke. The gauge is installed in a location that is not readily accessible by personnel. The normal position for the gauge is open. The gauge is currently open and in use. The licensee can manually close the shutter if needed. There were no personnel exposures.
The licensee has contacted the manufacturer to repair the cable.
The gauge is a Termo MeasureTech Model 5202, Serial Number B2813, containing 200 mCi of Cs-137.
Power Reactor
Event Number: 49585
Facility: DRESDEN
Region: 3 State: IL
Unit: [] [2] []
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: KYLE KOLLER
HQ OPS Officer: CHARLES TEAL
Region: 3 State: IL
Unit: [] [2] []
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: KYLE KOLLER
HQ OPS Officer: CHARLES TEAL
Notification Date: 11/26/2013
Notification Time: 19:02 [ET]
Event Date: 11/26/2013
Event Time: 14:00 [CST]
Last Update Date: 11/26/2013
Notification Time: 19:02 [ET]
Event Date: 11/26/2013
Event Time: 14:00 [CST]
Last Update Date: 11/26/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
HIRONORI PETERSON (R3DO)
HIRONORI PETERSON (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
LEAKAGE DISCOVERED ON ELECTROMATIC RELIEF VALVE DURING HYDROSTATIC TESTING
"On November 26, 2013, with Unit 2 shutdown for refueling, leakage was identified on the 2-0203-3C Electromatic Relief Valve (ERV) during a Reactor Pressure Vessel (RPV) pressure test. The leak is located on the line connecting the ERV main body to the pilot valve, and is approximately 1 drop per second. Each unit is designed with relief valves which actuate to control reactor coolant system pressure during transient conditions and are located on the main steam lines between the reactor vessel and the first isolation valve within the drywell. The cause of this event is under investigation.
"The condition is being reported under 50.72(b)(3)(ii)(A) given the defect was associated with the primary coolant system pressure boundary.
"The NRC Resident Inspector has been notified."
"On November 26, 2013, with Unit 2 shutdown for refueling, leakage was identified on the 2-0203-3C Electromatic Relief Valve (ERV) during a Reactor Pressure Vessel (RPV) pressure test. The leak is located on the line connecting the ERV main body to the pilot valve, and is approximately 1 drop per second. Each unit is designed with relief valves which actuate to control reactor coolant system pressure during transient conditions and are located on the main steam lines between the reactor vessel and the first isolation valve within the drywell. The cause of this event is under investigation.
"The condition is being reported under 50.72(b)(3)(ii)(A) given the defect was associated with the primary coolant system pressure boundary.
"The NRC Resident Inspector has been notified."
Power Reactor
Event Number: 49580
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: RICK DAVIDSON
HQ OPS Officer: JOHN SHOEMAKER
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: RICK DAVIDSON
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 11/26/2013
Notification Time: 05:08 [ET]
Event Date: 11/26/2013
Event Time: 04:00 [CST]
Last Update Date: 11/26/2013
Notification Time: 05:08 [ET]
Event Date: 11/26/2013
Event Time: 04:00 [CST]
Last Update Date: 11/26/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
HIRONORI PETERSON (R3DO)
HIRONORI PETERSON (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
DISCHARGE CANAL RADIATION MONITOR REMOVED FROM SERVICE
"Planned preventative maintenance on the discharge canal piping will remove the discharge canal radiation monitor from service. This represents a loss of emergency assessment capability under NUREG-1022, revision 3, specific to RU1.1, RU1.2, RA1.1, and RA1.2. The planned maintenance is expected to last 13 hours.
"The NRC Senior Resident Inspector was notified [by the licensee] prior to removing the discharge canal radiation monitor from service."
"Planned preventative maintenance on the discharge canal piping will remove the discharge canal radiation monitor from service. This represents a loss of emergency assessment capability under NUREG-1022, revision 3, specific to RU1.1, RU1.2, RA1.1, and RA1.2. The planned maintenance is expected to last 13 hours.
"The NRC Senior Resident Inspector was notified [by the licensee] prior to removing the discharge canal radiation monitor from service."